WO2001018822A1 - Method for producing nuclear fuel pellets of the mox type - Google Patents

Method for producing nuclear fuel pellets of the mox type Download PDF

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Publication number
WO2001018822A1
WO2001018822A1 PCT/EP2000/008057 EP0008057W WO0118822A1 WO 2001018822 A1 WO2001018822 A1 WO 2001018822A1 EP 0008057 W EP0008057 W EP 0008057W WO 0118822 A1 WO0118822 A1 WO 0118822A1
Authority
WO
WIPO (PCT)
Prior art keywords
beads
preparing
thermal treatment
powder
anyone
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Ceased
Application number
PCT/EP2000/008057
Other languages
English (en)
French (fr)
Inventor
Didier Haas
Claude Fuchs
Serge Fourcaudot
François Charollais
Joseph Somers
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
European Community EC Luxemburg
Original Assignee
European Community EC Luxemburg
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by European Community EC Luxemburg filed Critical European Community EC Luxemburg
Priority to CA002382626A priority Critical patent/CA2382626C/en
Priority to JP2001522550A priority patent/JP5153981B2/ja
Priority to US10/031,407 priority patent/US6733699B1/en
Publication of WO2001018822A1 publication Critical patent/WO2001018822A1/en
Priority to NO20021088A priority patent/NO334069B1/no
Anticipated expiration legal-status Critical
Ceased legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C21/00Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
    • G21C21/02Manufacture of fuel elements or breeder elements contained in non-active casings
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Definitions

  • MIMAS "Mlcron- ized MASter Blend” - see for example D. Haas, M. Lippens “MOX FUEL FABRICATION AND IN-REACTOR PERFORMANCE", Proc. of the Internat. Conference on Future Nuclear Systems, GLOBAL 97, p.489 a 494).
  • MIMAS "Mlcron- ized MASter Blend” - see for example D. Haas, M. Lippens “MOX FUEL FABRICATION AND IN-REACTOR PERFORMANCE", Proc. of the Internat. Conference on Future Nuclear Systems, GLOBAL 97, p.489 a 494).
  • This separate preparation of a powder free of plutonium reduces the volume of plutonium containing powder that has to be milled, and allows the production of fuel pellets of various plutonium contents with a unique plutonium treatment chain by changing only the rate of admixed uranium powder.
  • the present invention aims to overcome these drawbacks and to propose a method as indicated above which leads to fuel pellets of the MOX type in which the distribution of plutonium throughout the pellet is substantially more homogeneous.
  • the method according to the invention implies the separate preparation of a Pu-U oxide powder on the one hand and an uranium oxide powder free of plutonium on the other hand.
  • the Pu-U oxide powder is prepared conventionally by mechanically milling Pu0 2 and U0 2 materials, whereas the U0 2 powder is prepared as follows: To an aqueous solution of uranyl nitrate small amounts, i.e. between 0.5 and 2 wt%, of organic thickeners are added, such as ethocel, dextran, polyvinyl alcohol, such that the viscosity of the solution is adjusted to values between 20 and 100 centipoise. There-after, this solution is dispersed into droplets, which are introduced into an ammonia bath. In this bath, due to the network formed by the long chain organic polymers, precipitation occurs within the original droplets, so that nearly spherical beads are formed.
  • organic thickeners such as ethocel, dextran, polyvinyl alcohol
  • these beads depends on the size of the droplets produced during dispersion. In a preferred embodiment these beads present diameters of between 20 and 50 ⁇ m. These beads are then washed to remove nitrate salts (ammonium nitrate salts in the above example) and organic polymers, and are subjected to an azeotropic distil- lation using an immiscible organic solvent such as C 2 C1 4 to remove water.
  • nitrate salts ammonium nitrate salts in the above example
  • organic polymers organic polymers
  • the beads are in a hydroxide form, from which they are converted to oxide by a thermal treatment of between 2 and 6 hours duration and at about 400°C in air. Thereby residual organic polymers are pyrolysed.
  • the beads are then again submitted to a thermal treatment of between 4 and 8 hours duration, this time at about 800°C and in a reducing atmosphere of Ar/5%H 2 , to convert U 3 0 8 to U0 2 .
  • the beads can be produced by conventional uranium processing facilities (no ⁇ contamination). They are free flowing, dust free and do not require any further mechanical treatment such as milling prior to mixing with the powder containing plutonium.
  • the homogeneity of the finally produced fuel can further be enhanced by sieving the beads and retaining only beads with diameters in the range of 20 to 50 ⁇ m. Alternatively this result can also be achieved by using a droplet dispersion device which produces droplets of well defined size such that the bead diameters remain within said range and no sieving becomes necessary.
  • pellets are then sintered at high temperature, preferably at 1700°C, in a humidified Ar/H 2 atmosphere, the hydrogen content of which lies between 1 and 6% and the water vapour introduction should result in a ratio of the partial H 2 pressure to the water vapour partial pressure of between 20 and 60.
  • the water allows to control the oxygen potential of the gas atmosphere which results in an enhanced diffusion and in a more homogeneous fuel thus enabling a longer burn-up in the reactor.
  • the powder containing an excess content of plutonium can be prepared in the same way as above described for the uranium oxide powder, but by starting with uranyl-plutonium nitrate instead of uranyl nitrate.
  • the inventive method can be realised in conventional MOX fabrication facilities and conserves all the advantages of the MIMAS process but does not suffer from the drawbacks of this process as mentioned above.

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Manufacturing & Machinery (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Catalysts (AREA)
  • Solid Fuels And Fuel-Associated Substances (AREA)
  • Organic Low-Molecular-Weight Compounds And Preparation Thereof (AREA)
  • Pharmaceuticals Containing Other Organic And Inorganic Compounds (AREA)
  • Acyclic And Carbocyclic Compounds In Medicinal Compositions (AREA)
PCT/EP2000/008057 1999-09-06 2000-08-17 Method for producing nuclear fuel pellets of the mox type Ceased WO2001018822A1 (en)

Priority Applications (4)

Application Number Priority Date Filing Date Title
CA002382626A CA2382626C (en) 1999-09-06 2000-08-17 Method for producing nuclear fuel pellets of the mox type
JP2001522550A JP5153981B2 (ja) 1999-09-06 2000-08-17 Moxタイプの核燃料ペレットの製法
US10/031,407 US6733699B1 (en) 1999-09-06 2000-08-17 Method for producing nuclear fuel pellets of the MOX type
NO20021088A NO334069B1 (no) 1999-09-06 2002-03-05 Fremgangsmåte ved fremstilling av kjernebrenselpellets av MOX-type

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
EP99116886A EP1081716B1 (en) 1999-09-06 1999-09-06 Method for producing nuclear fuel pellets of the mox type
EP99116886.5 1999-09-06

Publications (1)

Publication Number Publication Date
WO2001018822A1 true WO2001018822A1 (en) 2001-03-15

Family

ID=8238868

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/EP2000/008057 Ceased WO2001018822A1 (en) 1999-09-06 2000-08-17 Method for producing nuclear fuel pellets of the mox type

Country Status (11)

Country Link
US (1) US6733699B1 (https=)
EP (1) EP1081716B1 (https=)
JP (1) JP5153981B2 (https=)
AT (1) ATE266892T1 (https=)
CA (1) CA2382626C (https=)
DE (1) DE69917257T2 (https=)
DK (1) DK1081716T3 (https=)
ES (1) ES2219963T3 (https=)
NO (1) NO334069B1 (https=)
PT (1) PT1081716E (https=)
WO (1) WO2001018822A1 (https=)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107845432A (zh) * 2016-09-20 2018-03-27 中核四〇四有限公司 一种mox球磨粉末混料方法
CN107845433A (zh) * 2016-09-20 2018-03-27 中核四〇四有限公司 一种mox粉末成形剂与润滑剂添加方法

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE10138874A1 (de) * 2001-08-08 2003-03-06 Framatome Anp Gmbh Verfahren zur Herstellung eines Mischoxid-Kernbrennstoff-Pulvers und eines Mischoxid-Kernbrennstoff-Sinterkörpers
JP4334316B2 (ja) 2003-10-16 2009-09-30 原子燃料工業株式会社 重ウラン酸アンモニウム粒子製造装置
JP4639063B2 (ja) * 2004-08-06 2011-02-23 原子燃料工業株式会社 滴下原液
WO2005061387A1 (ja) * 2003-12-24 2005-07-07 Nuclear Fuel Industries, Ltd. 滴下原液、滴下原液の調製方法、硝酸ウラニル溶液の調製方法、及びポリビニルアルコール溶液の調製方法
FR3030500B1 (fr) * 2014-12-18 2019-07-05 Areva Nc Procede de fabrication d'une pastille d'au moins un oxyde metallique, son utilisation comme combustible nucleaire
FR3163368A1 (fr) * 2024-06-17 2025-12-19 Commissariat A L'energie Atomique Et Aux Energies Alternatives Procédé de préparation d'une poudre comprenant un ou plusieurs oxydes choisis parmi l'oxyde d'uranium UO2, l'oxyde de plutonium PuO2 et les oxydes d'actinides mineurs

Citations (7)

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GB1480427A (en) * 1973-10-26 1977-07-20 Agip Nucleare Spa Production of microspheres
US4202793A (en) * 1973-10-26 1980-05-13 Agip Nucleare S.P.A. Production of microspheres of thorium oxide, uranium oxide and plutonium oxide and their mixtures containing carbon
US4382885A (en) * 1981-04-24 1983-05-10 The United States Of America As Represented By The United States Department Of Energy Method for producing nuclear fuel
US4384990A (en) * 1979-06-02 1983-05-24 Kemforschungsanlage Julich GmbH Uranyl nitrate pouring solution for producing nuclear fuel particles and a method for its preparation
US4571315A (en) * 1978-05-05 1986-02-18 Agip Nucleare S.P.A. Preparing ceramic material pellets
FR2622343A1 (fr) * 1987-10-26 1989-04-28 Commissariat Energie Atomique Procede de fabrication de pastilles de combustible nucleaire a base d'oxyde mixte (u, pu)o2
EP1020873A1 (en) * 1999-01-18 2000-07-19 European Community A method for tailoring the density of nuclear fuel pellets

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DD33300A (https=) *
SE328559B (https=) * 1967-03-01 1970-09-21 Nukem Gmbh
JPS61281019A (ja) * 1985-06-04 1986-12-11 Mitsubishi Metal Corp 六フツ化ウランを二酸化ウランに変換する方法
IT1187702B (it) * 1985-07-23 1987-12-23 V A M P Srl Processo per la preparazione di concentrati di additivi per composizioni a base di polimeri,e prodotti cosi' ottenuti
JPH0653572B2 (ja) * 1986-05-27 1994-07-20 三菱マテリアル株式会社 六フツ化ウランから二酸化ウランを製造する方法
US5139709A (en) * 1991-02-04 1992-08-18 Institute Of Nuclear Energy Research, Chinese Atomic Energy Council, Taiwan Process for converting uranyl compounds to UO2 via ADU
JP3091555B2 (ja) * 1992-02-21 2000-09-25 原子燃料工業株式会社 核燃料体の製造方法
JPH05256973A (ja) * 1992-03-13 1993-10-08 Nuclear Fuel Ind Ltd 凝固液滴の選別方法及び凝固液滴選別装置
JP2836711B2 (ja) * 1992-03-27 1998-12-14 原子燃料工業株式会社 重ウラン酸アンモニウム粒子の製造方法と製造装置
JP2662359B2 (ja) * 1993-07-23 1997-10-08 動力炉・核燃料開発事業団 核燃料ペレットの製造方法
JP2907694B2 (ja) * 1993-09-09 1999-06-21 核燃料サイクル開発機構 核燃料ペレットの製造方法
JPH0862362A (ja) * 1994-08-25 1996-03-08 Nuclear Fuel Ind Ltd Moxペレット成型体の製造方法
JPH08231226A (ja) * 1995-02-27 1996-09-10 Nippon Nuclear Fuel Dev Co Ltd Uo2粉末の製造方法
FR2738076B1 (fr) * 1995-08-25 1997-09-26 Commissariat Energie Atomique Procede de fabrication de pastilles de combustible nucleaire a base d'oxyde mixte (u, pu)o2 avec addition d'un produit organique soufre

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1480427A (en) * 1973-10-26 1977-07-20 Agip Nucleare Spa Production of microspheres
US4202793A (en) * 1973-10-26 1980-05-13 Agip Nucleare S.P.A. Production of microspheres of thorium oxide, uranium oxide and plutonium oxide and their mixtures containing carbon
US4571315A (en) * 1978-05-05 1986-02-18 Agip Nucleare S.P.A. Preparing ceramic material pellets
US4384990A (en) * 1979-06-02 1983-05-24 Kemforschungsanlage Julich GmbH Uranyl nitrate pouring solution for producing nuclear fuel particles and a method for its preparation
US4382885A (en) * 1981-04-24 1983-05-10 The United States Of America As Represented By The United States Department Of Energy Method for producing nuclear fuel
FR2622343A1 (fr) * 1987-10-26 1989-04-28 Commissariat Energie Atomique Procede de fabrication de pastilles de combustible nucleaire a base d'oxyde mixte (u, pu)o2
EP1020873A1 (en) * 1999-01-18 2000-07-19 European Community A method for tailoring the density of nuclear fuel pellets

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
D. HAAS ET AL.: "MOX fuel fabrication and in-reactor performance", PROC. INT. CONF. ON FUTURE NUCLEAR SYSTEMS, GLOBAL 97, pages 489 - 494, XP000869930 *

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107845432A (zh) * 2016-09-20 2018-03-27 中核四〇四有限公司 一种mox球磨粉末混料方法
CN107845433A (zh) * 2016-09-20 2018-03-27 中核四〇四有限公司 一种mox粉末成形剂与润滑剂添加方法
CN107845432B (zh) * 2016-09-20 2019-09-17 中核四〇四有限公司 一种mox球磨粉末混料方法
CN107845433B (zh) * 2016-09-20 2019-09-17 中核四〇四有限公司 一种mox粉末成形剂与润滑剂添加方法

Also Published As

Publication number Publication date
EP1081716A1 (en) 2001-03-07
NO20021088L (no) 2002-05-06
DE69917257D1 (de) 2004-06-17
NO20021088D0 (no) 2002-03-05
DK1081716T3 (da) 2004-09-13
DE69917257T2 (de) 2005-05-19
PT1081716E (pt) 2004-08-31
CA2382626C (en) 2008-11-25
US6733699B1 (en) 2004-05-11
EP1081716B1 (en) 2004-05-12
ATE266892T1 (de) 2004-05-15
ES2219963T3 (es) 2004-12-01
JP2003509659A (ja) 2003-03-11
JP5153981B2 (ja) 2013-02-27
CA2382626A1 (en) 2001-03-15
NO334069B1 (no) 2013-12-02

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